ASTM C1174-17
(Practice)Standard Practice for Evaluation of the Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste
Standard Practice for Evaluation of the Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste
SIGNIFICANCE AND USE
5.1 This practice supports the development of material behavior models that can be used to estimate performance of the EBS materials during the post-closure period of a high-level nuclear waste repository for times much longer than can be tested directly. This practice is intended for modeling the degradation behaviors of materials proposed for use in an EBS designed to contain radionuclides over tens of thousands of years and more. There is both national and international recognition of the importance of the use and long-term performance of engineered materials in geologic repository design. Use of the models developed following the approaches described in this practice is intended to address established regulations, such as:
5.1.1 U.S. Public Law 97–425, the Nuclear Waste Policy Act of 1982, provides for the deep geologic disposal of high-level radioactive waste through a system of multiple barriers. These barriers include engineered barriers designed to prevent the migration of radionuclides out of the engineered system, and the geologic host medium that provides an additional transport barrier between the engineered system and biosphere. The regulations of the U.S. Nuclear Regulatory Commission for geologic disposal require a performance confirmation program to provide data through tests and analyses, where practicable, that demonstrate engineered systems and components that are designed or assumed to act as barriers after permanent closure are functioning as intended and anticipated.
5.1.2 IAEA Safety Requirements specify that engineered barriers shall be designed and the host environment shall be selected to provide containment of the radionuclides associated with the wastes.
5.1.3 The Swedish Regulatory Authority has provided general advice to the repository developer that the application of best available technique be followed in connection with disposal, which means that the siting, design, construction, and operation of the repository and appurten...
SCOPE
1.1 This practice addresses how various test methods and data analyses can be used to develop models for the evaluation of the long-term alteration behavior of materials used in engineered barrier system (EBS) for the disposal of spent nuclear fuel (SNF) and other high-level nuclear waste in a geologic repository. The alteration behavior of waste forms and EBS materials is important because it affects the retention of radionuclides within the disposal system either directly, as in the case of waste forms in which the radionuclides are initially immobilized, or indirectly, as in the case of EBS containment materials that restrict the ingress of groundwater or the egress of radionuclides that are released as the waste forms degrade.
1.2 The purpose of this practice is to provide a scientifically-based strategy for developing models that can be used to estimate material alteration behavior after a repository is permanently closed (that is, the post-closure period) because the timescales involved with geological disposal preclude direct validation of predictions.
1.3 This practice also addresses uncertainties in materials behavior models and the impact on the confidence in the EBS design criteria, the scientific bases of alteration models, and repository performance assessments using those models. This includes the identification and use of conservative assumptions to address uncertainty in the long-term performance of materials.
1.3.1 Steps involved in evaluating the performance of waste forms and EBS materials include problem definition, laboratory and field testing, modeling of individual and coupled processes, and model confirmation.
1.3.2 The estimates of waste form and EBS material performance are based on models derived from theoretical considerations, expert judgments, and interpretations of data obtained from tests and analyses of appropriate analogs.
1.3.3 For the purpose of this practice, tests are ...
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Designation: C1174 − 17
Standard Practice for
Evaluation of the Long-Term Behavior of Materials Used in
Engineered Barrier Systems (EBS) for Geological Disposal
1
of High-Level Radioactive Waste
This standard is issued under the fixed designation C1174; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope considerations, expert judgments, and interpretations of data
obtained from tests and analyses of appropriate analogs.
1.1 This practice addresses how various test methods and
1.3.3 For the purpose of this practice, tests are categorized
data analyses can be used to develop models for the evaluation
according to the information they provide and how it is used
of the long-term alteration behavior of materials used in
for model development, support, and use. These tests may
engineered barrier system (EBS) for the disposal of spent
include but are not limited to: accelerated tests, attribute tests,
nuclear fuel (SNF) and other high-level nuclear waste in a
characterization tests, confirmation tests, and service condition
geologicrepository.Thealterationbehaviorofwasteformsand
tests.
EBS materials is important because it affects the retention of
1.4 This standard does not purport to address all of the
radionuclides within the disposal system either directly, as in
safety concerns, if any, associated with its use. It is the
the case of waste forms in which the radionuclides are initially
responsibility of the user of this standard to establish appro-
immobilized, or indirectly, as in the case of EBS containment
priate safety and health practices and determine the applica-
materials that restrict the ingress of groundwater or the egress
bility of regulatory requirements prior to use.
of radionuclides that are released as the waste forms degrade.
1.5 This international standard was developed in accor-
1.2 The purpose of this practice is to provide a
dance with internationally recognized principles on standard-
scientifically-based strategy for developing models that can be
ization established in the Decision on Principles for the
used to estimate material alteration behavior after a repository
Development of International Standards, Guides and Recom-
is permanently closed (that is, the post-closure period) because
mendations issued by the World Trade Organization Technical
the timescales involved with geological disposal preclude
Barriers to Trade (TBT) Committee.
direct validation of predictions.
2. Referenced Documents
1.3 This practice also addresses uncertainties in materials
behavior models and the impact on the confidence in the EBS 2
2.1 ASTM Standards:
design criteria, the scientific bases of alteration models, and
C859 Terminology Relating to Nuclear Materials
repository performance assessments using those models. This
C1285 Test Methods for Determining Chemical Durability
includes the identification and use of conservative assumptions
of Nuclear, Hazardous, and Mixed Waste Glasses and
to address uncertainty in the long-term performance of mate-
MultiphaseGlassCeramics:TheProductConsistencyTest
rials.
(PCT)
1.3.1 Steps involved in evaluating the performance of waste
C1682 Guide for Characterization of Spent Nuclear Fuel in
forms and EBS materials include problem definition, labora-
Support of Interim Storage, Transportation and Geologic
tory and field testing, modeling of individual and coupled
Repository Disposal
processes, and model confirmation.
E177 Practice for Use of the Terms Precision and Bias in
1.3.2 The estimates of waste form and EBS material perfor-
ASTM Test Methods
mance are based on models derived from theoretical
E178 Practice for Dealing With Outlying Observations
E583 Practice for Systematizing the Development of
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel
2
and High Level Waste. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved July 1, 2017. Published August 2017. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1991. Last previous edition approved in 2013 as C1174 – 07 (2013). Standards volume information, refer to the standard’s Document Summary page on
DOI: 10.1520/C1174-17. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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C1174 − 17
(ASTM) Voluntary Consensus Standards for the Solution accepted in dictionaries of the English lang
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: C1174 − 07 (Reapproved 2013) C1174 − 17
Standard Practice for
PredictionEvaluation of the Long-Term Behavior of
Materials, Including Waste Forms, Materials Used in
Engineered Barrier Systems (EBS) for Geological Disposal
1
of High-Level Radioactive Waste
This standard is issued under the fixed designation C1174; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This practice describes addresses how various test methods and data analyses can be used to develop models for the
predictionevaluation of the long-term alteration behavior of materials, such asmaterials used in engineered barrier system (EBS)
materials and waste forms, used in the geologic for the disposal of spent nuclear fuel (SNF) and other high-level nuclear waste
in a geologic repository. The alteration behavior of waste formforms and EBS materials is important because it affects the retention
of radionuclides by the disposal system. The waste form and EBS materials provide a barrier to release either directly (aswithin
the disposal system either directly, as in the case of waste forms in which the radionuclides are initially immobilized),immobilized,
or indirectly (asindirectly, as in the case of EBS containment materials that restrict the ingress of groundwater or the egress of
radionuclides that are released as the waste forms and EBS materials degrade).degrade.
1.1.1 Steps involved in making such predictions include problem definition, testing, modeling, and model confirmation.
1.1.2 The predictions are based on models derived from theoretical considerations, expert judgment, interpretation of data
obtained from tests, and appropriate analogs.
1.1.3 For the purpose of this practice, tests are categorized according to the information they provide and how it is used for
model development and use. These tests may include but are not limited to the following:
1.1.3.1 Attribute tests to measure intrinsic materials properties,
1.1.3.2 Characterization tests to measure the effects of material and environmental variables on behavior,
1.1.3.3 Accelerated tests to accelerate alteration and determine important mechanisms and processes that can affect the
performance of waste form and EBS materials,
1.1.3.4 Service condition tests to confirm the appropriateness of the model and variables for anticipated disposal conditions,
1.1.3.5 Confirmation tests to verify the predictive capacity of the model, and
1.1.3.6 Tests or analyses performed with analog materials to identify important mechanisms, verify the appropriateness of an
accelerated test method, and to confirm long-term model predictions.
1.2 The purpose of this practice is to provide a scientifically-based strategy for developing models that can be used to estimate
material alteration behavior after a repository is permanently closed (that is, the post-closure period) because the timescales
involved with geological disposal preclude direct validation of predictions.
1.3 The purpose of this practice is to provide methods for developing models that can be used for the prediction of materials
behavior over the long periods of time pertinent to the service life of a geologic repository as part of the basis for performance
assessment of the repository. This practice also addresses uncertainties in materials behavior models and the impact on the
confidence in the EBS design criteria, the scientific bases of alteration models, and repository performance assessments using those
models. This includes the identification and use of conservative assumptions to address uncertainty in the long-term performance
of materials.
1.3.1 Steps involved in evaluating the performance of waste forms and EBS materials include problem definition, laboratory and
field testing, modeling of individual and coupled processes, and model confirmation.
1.3.2 The estimates of waste form and EBS material performance are based on models derived from theoretical considerations,
expert judgments, and interpretations of data obtained from tests and analyses of appropriate analogs.
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and High
Level Waste.
Current edition approved April 1, 2013July 1, 2017. Published April 2013August 2017. Origi
...
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